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Journal Articles

Effect of hydrocarbons on the efficiency of catalytic reactor of detritiation system in an event of fire

Edao, Yuki; Sato, Katsumi; Iwai, Yasunori; Hayashi, Takumi

Journal of Nuclear Science and Technology, 53(11), p.1831 - 1838, 2016/11

 Times Cited Count:9 Percentile:58.60(Nuclear Science & Technology)

Journal Articles

The Oxidation performance test of detritiation system under existence of CO and CO$$_{2}$$

Kobayashi, Kazuhiro; Terada, Osamu*; Miura, Hidenori*; Hayashi, Takumi; Nishi, Masataka

Fusion Science and Technology, 48(1), p.476 - 479, 2005/07

 Times Cited Count:10 Percentile:55.20(Nuclear Science & Technology)

To construct the ITER with high safety and acceptability, it is necessary to establish and to ensure the tritium safe handling technology. The performance of the detritiation system at the off-normal events has not been confirmed well. To obtain performance data of detritiation system at the off normal events, the detritiation experiment was performed at TPL/JAERI using a scaled detritiation system for the oxidation performance test. The detritiation system consists of two oxidation catalyst beds (473K and 773K) and a molecular sieve drying absorber. Basic performance of the detritiation system for hydrogen and methane in air was evaluated under maximum ventilation flow rate. Obtained oxidation efficiency was more than 99.99% for hydrogen in the catalyst bed of 473K and more than 99.9% for methane in the 773K one, respectively. It was confirmed that these performances were maintained even under carbon dioxide , carbon monoxide if oxygen remained in the process gas.

Journal Articles

Design of the ITER tritium plant, confinement and detritiation facilities

Yoshida, Hiroshi; Glugla, M.*; Hayashi, Takumi; L$"a$sser, R.*; Murdoch, D.*; Nishi, Masataka; Haange, R.*

Fusion Engineering and Design, 61-62, p.513 - 523, 2002/11

 Times Cited Count:31 Percentile:85.15(Nuclear Science & Technology)

ITER tritium plant is composed of tokamak fuel cycle systems, tritium confinement and detritation systems. The tokamak fuel cycle systems, composed of various tritium sumsystems such as vacuum vessel cleaning gas processing, tokamak exhaust processing, hydrogen isotope separation, fuel storage, mixing and delivery, and external tritium receiving and long-term storage, has been designed to meet not only ITER operation scenarios but safety requirements (minimization of equipment tritium inventory and reduction of environmental tritium release at different off-normal events and accident scenarios). Multiple confinement design was employed because tritium easily permeates through metals (at $$>$$ 150 $$^{circ}$$C) and plastics (at ambient temperature) and mixed with moisture in room air. That is, tritium process equipment and piping are designed to be the primary confinement barrier, and the process equipments (tritium inventory $$>$$ 1 g) are surrounded by the secondary confinement barrier such as a glovebox. Tritium process rooms, which contains these facilities, form the tertiary confinement barrier, and equipped with emergency isolation valves in the heating ventillation and air conditioning ducts as well as atmosphere detritiation systems. This confinement approach has been applied to tokamak building, tritium building, and hotcell and radwaste building.

Journal Articles

Design study of feasible water detritiation systems for fusion reactor of ITER scale

Iwai, Yasunori; Yamanishi, Toshihiko; Okuno, Kenji; Yokogawa, Nobuhisa*; ; Yoshida, Hiroshi; O.K.Kveton*

Journal of Nuclear Science and Technology, 33(12), p.981 - 992, 1996/12

 Times Cited Count:29 Percentile:89.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Detritiation of air in a glove box with a newly developed compact tritium removal equipment

Yamaguchi, Koichi; ;

Journal of Nuclear Science and Technology, 19(11), p.948 - 952, 1982/00

 Times Cited Count:2 Percentile:32.43(Nuclear Science & Technology)

no abstracts in English

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